ML20137Q658
| ML20137Q658 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Hatch, Peach Bottom, Farley, 05000000 |
| Issue date: | 01/03/1986 |
| From: | Grimsley D NRC OFFICE OF ADMINISTRATION (ADM) |
| To: | Houghton T KMC, INC. |
| Shared Package | |
| ML20137Q664 | List: |
| References | |
| FOIA-85-771 NUDOCS 8602060350 | |
| Download: ML20137Q658 (2) | |
Text
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~qg UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
g E
WASHINGTON, D. C. 20555 JAN 3 1980 Mr. Thomas C. Houghton, Associate KMC, Inc.
801 18th Street, NW, Suite 300 IN RESPONSE REFER Washington, DC 20006 TO F01A-85-771
Dear Mr. Houghton:
This is in response to your letter dated November 21, 1985, in which you requested, pursuant to the Freedom of Information Act (F0IA), copies of certain Reactor Operator and Senior Reactor Operator license examination question and answer keys.
The documents are identified on the enclosed appendix and are being placed in the NRC Public Document Ronm (PDR) located at 1717 H Street, NW, Washington, DC 20555, in file folder F01A-85-771 in your name.
Sincerely, hp>.a ll 4
/
Donnie H. Grimsley, Director Division of Rules and Records Office of Administration
Enclosure:
As stated i
t I
0602060350 D60103 PDR FOIA HOUGHTO35-771 PDR
4 Re:
F01A-85-771 APPENDIX Documents Being'Placed in the PDR 1.
07/15/85 'SR0 Examination Question and Answer Key - Hatch I and 2.
l (123 pages) 2.
07/15/85 R0 Exanination Question and Answer Key - Hatch I and 2.
j (188 pages) 3.
08/05/85 R0 Examination Question and Answer Key - Farley 1 and 2.
(144 pages)
[
4.
11/06/84 SR0 Examination Question and Answer Key - Millstone I.
(31 pages)
)
5, 12/11/84 R0 Examination Question and Answer Key - Millstone II.
(40 pages) 6 6.
12/11/84 SR0 Examination Question and Answer Key - Millstone II.
(43pages) 7.
06/25/85 R0 Examination Question and Answer Key - Peach Bottom 2 and 3.
(33pages) t i
8.
06/25/85 SR0 Examination Question and Answer Key - Peach Bottom 2 and 3.
(32 pages)
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(l-0 September 9,1985 PECE
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,y I2 Georgia Power Company c
ATTN:
Mr. R. J. Kelly Executive Vice' President P. O. Box 4545 Atlanta, GA 30302 Gentlemen:
SUBJECT:
EDWIN I. HATCH EXAMINATION REPORT 321/0L-85-02 The NRC administered examinations on July 15-17, 1985, to employees of your company who had applied for licenses to operate the Edwin I. Hatch Nuclear Plant.
Additionally, the NRC administered requalification examinations to employees of your company who currently hold licenses to operate the Edwin I. Hatch Nuclear Plant. At the conclusion of the examinations, the examination questions and preliminary findings were discussed with those members of your staff identified in the Examination Report, Enclosure 1.
A table summarizing the examination results for each examined individual is provided as Enclosure 2.
Copies of the written replacement and requalification examination questions and answer keys are included in this report as Enclosures 3 and 4, respectively.
A Requalification Program Evaluation Report is included as Enclosure 5.
In accordance with 10 CFR 2.790(a), a copy of this letter and Enclosures 1, 3, and 4 will be placed in NRC's Public Document Room.
Enclosures 2 and 5 are exempt from public disclosure pursuant to 10 CFR 2.790(a) and will not be sent to the Public Document Room.
Should you have any questions concerning this letter, please contact us.
l Sincerely, (Original signed by VLBrownlee)
Virgil L. Brownlee, Chief Reactor Projects Branch 2 Division of Reactor Projects
Enclosures:
(See page 2) l 8 @ 4 N $ $ 2pp.150909 Fun a mmA ' 05000321 G
,1s43 lh
Georgia Power Company 2
September 9,1985
Enclosures:
1.
Examination Report 50-321/0L-85-02 2.
Table of Examination Results (Official Use Only - Privacy Act Information) 3.
SRO Exam Questions and Answer Key -
Replacement Exam 4.
RO/SRO Exam Questions and Answer Key - Requalification Exam 5.
Requalification Program Evaluation Report cc w/encis. 1, 2 & 5:
J, J. Badgett, Corporate Training Manager H. C. Nix, Site General Manager cc w/encis. 1, 2, 3, 4 & 5:
C. T. Moore, Site Training Supervisor bec w/encls. 1, c,
3, 4 & 5:
Senior Resident Inspector bec w/ enc 1. 1:
Project Manager, NRR State of Georgia M. King, EG&G Idaho bec w/encls. 1, 3 & 4:
Operating Licensing Branch, DHFS, NRR Document Control Desk RII RII RI RII ff pH W
C PRSh :bhg KBrockman B
lson CAJ 1an V
ciera 8/JT 85 8/%f/85 8/gj/85 8/ /85 8 f/85 f/325
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Septenter 16, 1985 Alabama Power Company p~"
f ATTN:
Mr. R. P. Mcdonald M rji 10 !C:33 Senior Vice President P. O. Box 2641 Birmingham, AL 35291-r-
Gentlemen:
SUBJECT:
FARLEY EXAMINATION REPORT 348 /0L-85-02 The NRC administered examinations on August 5 - 8, 1985, to employees of your company who had applied for licenses to operate the Farley Nuclear Plant. At the conclusion of the examinations, the examination questions and preliminary findings were discussed with those members of your staff identified in the Examination' Report, Enclosure 1.
A table summarizing the examination results for each examined individual is provided as Enclosure 2.
Copies of the written examination questions and answer key are included in this report as Enclosure 3.
In accordance with 10 CFR 2.790(a), a copy of this letter and Enclosures 1 and 3 will be placed in NRC's Public Document Room. Enclosure 2 is exempt from public disclosure pursuant to 10 CFR 2.790(a) and will not be sent to the Public Document Room.
Should you have any questions concerning this letter, please contact us.
Sincerely, (Original signed by SWeise)
David M. Verrelli, Chief Reactor Projects Branch 1 Division of Reactor Projects
Enclosures:
- 1. Examination Report 50-348/0L-85-02
- 2. Table of Examination Results (Official Use Only-Privacy Act Information)
- 3. RO/SRO Exam Questions and Answer Key ec w/encls. 1 & 2:
J. D. Woodard, Plant Manager cc w/encls. 1, 2, & 3:
L. Williams, Site Training Director bec w/encis: J e page 2) e-Aa 4-rA>?" 2g,
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t Alabama Power Company 2
September 16, 1985 bec w/encls. 1, 2, & 3:
Senior Resident Inspector bec w/ enc 1. 1:
Project Manager, NRR State of Alabama bec w/encls. 1 & 3:
Operator Licensing Branch, DHFS,NRR Document Control Desk RII RII RII RII RII WM0 fan:sa WGD ug as Ison CAJu an FCa 11 09/I/85 09/i/85 09/f0/85 09/ /85 09/jy/85
/2 1
.t FES 6 1965 Docket No 50-336
- _ _.. -,s m
-s Northeast Nuclear Energy Company ATTN:
Mr. W. G. Counsil r
Senior Vice President - Nuclear Engineering and Operations Group P. O. Box 270 Hartford, Connecticut 06141-0270
- Gentlemen:
SUBJECT:
EXAMINATION REPORT NO. 50-336/84-27(0L)
This transmits the Examination Report of Operator Licensing Examinations conducted by USNRC Region I at the Millstone 2 Facility the week of December 10, 1984.
At the exit interview held on December 13, 1984 the preliminary results of these examinations were discussed.
No reply to this letter is required.
Your cooperation in this matter is appreciated.
Sincerely, y:.6_ - c.sa*187 8 E'dward C. Wenzinger, Chief Projects Branch No. 3 Division of Reactor Projects
Enclosure:
Examination Report No. 50-336/84-27(0L)
Attachmeat: Written Examination (s) and Answer (S) Key (SR0/RO) cc: w/ enclosures Plant Superintendent Plant Training Manager Senior Resident Inspector Public Document Room (PDR)
Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
State of Connecticut
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hogos M v u ) D 5ooo336
]un muvun PDR OFFICIAL RECORD COPY HILLSTONE EXAM TRIP - 0001.0.0 (f,0 i'
\\
Northeast Nuclear Energy Company 2
bec: w/o Attachment to Enclosure DRP Section Chief Examiner D. Beckham, OLB/DHFS, NRR OL File 12.0 Region I Docket Room (w/ concurrences)
. Master Exam File D. Weiss, LFMS B. Gore, PNL h*1 RYDRP RI:DRPt' RI:0RP RI:_Q'RP RI:DRP Kister Wenzinger Dudley/djh Ke Ar Mcggbe 143/85 1/piB5 1M/85 1/3)/85 1/f/85
<1r OFFICIAL RECORD COPY MILLSTONE EXAM TRIP - 0004.0.0 09/21/84
U. S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT NO.
84-27(OL)
FACILITY DOCKET NO. 50-336
, FACILITY LICENSE NO. DPR-65 LICENSEE:
Northeast Nuclear Energy Company P. O. Box 270 Hartford, Connecticut 06141-0270 FACILITY: Millstone 2 EXAMINATION DATES: December 10-13, 1984
': ~s M c awi M 3 JAfi.: ; V CHIEF EXAMINER:
Noel Dudley Date Lead Reactor Engineer (Examiner) 4 4.x,:
P.+
1 JAli 2%
REVIEWED BY:
Chief, Project Section 1C Date Vr:4 M 51t,n1Ms FEE APPROVED BY:
dM
~'
Chief, Project Branch No. 1 Date
SUMMARY
- Twelve candidates were examined and seven R0 and five SRO licenses were issued.
_m& ~ st. n-o. q (n
,,36 I
OFFICIAL RECORD COPY MILLSTONE EXAM TRIP - 0005.0.0 09/21/84
2 REPORT DETAILS TYPE OF EXAMS:
Initial Replacement X
Requalification EXAM RESULTS:
l RO l
SR0 l
Inst. Cert l Fuel Handler l l
Pass / Fail l
Pass / Fail l
Pass / Fail l
Pass / Fail l
I I
I I
I I
I I
I I
I l Written Exam I 7/0 1
5/0 l
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I I
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l l Oral Exam l
7/0 1
5/0 l
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7/0 1
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CHIEF EXAMINER AT SITE:
N. Dudley 2.
OTHER EXAMINERS:
J. Upton. PNL J. Boegel, PNL J. Smith, PNL 3.
PERSONS EXAMINED R0 SRO l
J. M. Bergin J. D. Becker G. A. Beskop D. A. Ekeren C. D. Hackman J. J. Parillo i
J. S. Kunze K. Truesdale J. W. Riley J. A. Sloan W. H. Seifert C. L. Zorn OFFICIAL RECORD COPY MILLSTONE EXAM TRIP - 0005.1.0 09/21/84 L
3 1.
Summary of generic strengths or deficiencies noted from grading of written exams:
Weaknesses were found in a majority of candidates in the following areas:
1.
Reasons for programming pressurizer level in terms of design.
2.
Type of detectors used on radiation monitoring systems.
3.
The requirement for bypassing pressurizer high pressure trip on failure of pressurizer pressure instrument.
4 Reasons for procedural cautions in the CVCS and quench tank operating procedures.
5.
The use of the EPIP in determining the types of notifications required.
2.
Improvements noted in training programs as a result of prior operator licensing examinations / suggestions, ete:
The facility has greatly improved the quality of candidates sitting for licensing examinations as demonstrated by the improved pass rate.
The issuance of badges to examiners expedited the operational examinations.
3.
Personnel Present at Exit Interview:
NRC Personnel N. Dudley, Lead Reactor Engineer (Examiner)
T. Shediosky, Senior Resident Inspector Facility personnel R. Test, Director Nuclear Training K. Parkinson, Training Supervisor M. Wilson, Assistant Training Supervisor, Unit 2 4.
Summary of NRC Comments made at exit interview:
The names of the persons who were clear passes on the oral portion of the examination will be provided to the training department by the NRC contract examiners upon completion of all oral examinations.
OFFICIAL RECORD COPY MILLSTONE EXAM TRIP - 0006.0.0 09/21/84
4 5.
CHANGES MADE TO WRITTEN EXAM Question No.
Change Reason 1.08a Change " inches" to Changes rod position
" steps". Add "(Assume indication units to be plant HFP Boron)".
specific. Specifies boron concentration to eliminate requirement to interpolate on graph.
2.02 Answer After " steam generator Modify answer to incorporate water level will rise" the short term effect of add "then be returned swell ard the long term to the set point by.
effects of an increased steam FWRCS." After " feed-flow.
water-flowrate will decrease." Add "(+0.2) since steam flow increases feed flowrate will eventually increase (0.3)."
2.06c Answer Add "(RCP or letdown Provides alternate answer for Cooling heat exchanger temperature band when the (300"F to 350'F) shutdown heat exchanger is not aligned by procedure.
2.10 Answer Change "56.2% and Provides SIT tank level 58.7%" to "1080 cu.ft.
requirements in. units used and 1190 cu.ft."
in Technical Specifications.
3.02 and Change " inches" to Changes rod position 6.04
" steps" and " Tref" indications to be plant to "Tave".
specific.
Provides parameter which will change if electrical output is constant.
3.02b Answer Change " turbine" to Corrects answer to reflect
" cycle",
difference between changes in cycle and turbine efficiency when condenser vacuum is increased.
3.04 Change "H 0" to "#2".
Corrects identification of 2
3.04b Answer Add "SRAS".
The Sump Recirculation and Actuation Signal will be 6.06b Answer activated on an RWST level of 8%; ESAS system description, page 6.
OFFICIAL RECORD COPY MILLSTONE EXAM TRIP - 0009.0.0 09/21/84
5 Ouestion No.
Change Reason 3.05b Answer Change " low reactor Corrects answers from coolant flow" to "SG response for SG differential pressure".
pressure instrument _to proper response for SG pressure instrument.
3.05c Answer Add "and TM/LP".
Includes TM/LP channel since it is tripped.
3.07 Answer Add "or mainfeed Provides alternate answer and 6.09 Answer available" in accordance with E0P 2537, Loss of ALL Feedwater.
4.01b Answer Add "4. SG SBCS (+0.5)
Provides additional response cooldown to <520*F and for radioactive release from isolate (+0.5)".
the steam side of the SG.
4.03a Answer Add " change in MW".
Recognizes that electrical output will change with a change in condenser vacuum.
4.03b Answer
' Add "8. Reduce load; Incorporates two additional
- 9. Verify proper actions contained in AOP 2574 operation of vacuum Loss of Condenser Vacuum.
breakers".
4.04d Answer Change "3 MREM" to Corrects exposure limit to "1.25 rem".
value specified in 10 CFR 20.
5.02 Answer Change "1326" to "1357" Corrects math errors.
and "924" to "893".
5.03 Change " inches" to Changes rod position
" steps".
indication units to be plant specific.
6.04b Answer Change to read Corrects answer to reflect
" Increase (+0.5) be-difference between changes in cause the reactor cycle and turbine efficiency power had to in-when condenser vacuum crease due to de-increases, crease cycle ef ficiency (+0.5).
6.04d Answer Add "or increase due Provides alternate answer to change in ASI for effects of plant caused by rod pull."
parameters on TM/LP pressure set point.
OFFICIAL RECORD COPY MILLSTONE EXAM TRIP - 0010.0.0 09/21/84
o 6
Question No.
Change Reason 7.08a Answer Add "4. SJAE [0.5]
Provides additional responses align to EBFAS and for radioactive release from Unit I stack [0.5];
the steam side of the SG.
- 5. Atmospheric Dumps
[0.5] reduce Tave and isolate SG".
8.01 Change " Tank" to " Pool". Provides plant specific nomenclature for clarity.
8.01 Answer Change first sentence Provides procedure and to " Intent Procedure nomenclature specific to change is initiated".
facility.
8.02 Add "at 500 MREM /hr" Provides additional infor-af ter " air-monitor mation needed to classify the a l a rm".
event.
8.05a Answer Delete last sentence.
Information not required by question.
8.09a&e Change "one hour" Correct classification to Answer to "immediate".
correspond to EPIP 4701 Emergency Plan Implementation Procedure requirements.
Attachments:
s C
1.
Written Examination (s) and Answer Key (s) (SR 2.
Facility comments OFFICIAL RECORD COPY MILLSTONE EXAM TRIP - 0010.0.1 09/21/84
s..
Docket No. 50-245 JAN 151965 Northeast Nuclear Energy Company ATTN: Mr. W. G. Counsil
)
Senior Vice President - Nuclear Engineering and Operations Group P.O. Box 270 Nartford, Connecticut 06141-0270 Gentlemen:
SUBJECT:
EXAMINATION REPORT NO. 50-245/84-22 (OL)
This transmits the Examination Report of Operator Licensing Examinations conducted by USNRC Region I at the Millstone I Facility the week of November 5, 1984. At the exit interview, held on November 8,1984, the preliminary results of these examinations were discussed.
No reply to this letter is required.
Your cooperation in this matter is appreciated.
Sincerely, OriginalSii;JE U8 E. Wenzinger, Chief Reactor Projects Section IA Projects Branch No. 1 Division of Project and Resident Programs
Enclosure:
l Examination Report No. 50-245/84-22 (OL) w/ attachments l
cc: w/ enclosures Plant Superintendent Plant Training Manager Senior Resident Inspector Public Document Room (PDR) l Local Public Document Room (LPDR) l-Nuclear Safety Information Center (NSIC)
State of Connecticut l
OFFICIAL RECORD COPY MILLSTONE 1 EXAM RPT - 0001.0.0 09/21/84 hy 15
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r un am vauv0245 l
e Pon 1
Northeast Nuclear Energy Company 2
bec: w/o enclosures DPRP Section Chief Examiner D. Beckham, OLB/DHFS, NRR OL File 12.0 Region I Docket Room (w/ concurrences)
Master Exan File D. Weiss, L"MB RI:DFRPN RI:DPRP RI:DPRP RI:
RI:DPRP McCg Banavitch/djh Ber La e K
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OFFICIAL RECORD COPY MILLSTONE 1 EXAM RPT - 0004.0.0 09/21/84 l
U. S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT NO. 84-22 FACILITY DOCKET NO. 50-245 FACILITY LICENSE NO. DPR-21 LICENSEE: Northeast Nuclear Energy Company P.O. Box 270 Hartford, Connecticut 06141-0270 FACILITY: Millstone I EXAMINATION DATES: November 5-8, 1984 Originalt
[fNd //)v M,.
JAN 413e5 CHIEF EXAMINER:
John Berry, Untef BWR Examiner Date
~'
...r..:
APPROVED BY:
[, d[ddt' Chief, Project Section ID Date
SUMMARY
- The following report contains the results of the Operator Licensing Examinations administered at the Millstone I facility the week of November 5, 1984.
Two Upgrade Senior Reactor Operator candidates were examined.
Both candidates successfully completed the written and oral examinations adminis-tered.
An inspection of the Requalification Training Program was conducted by the examiners on November 7,
1984.
The results of the inspection showed no significant deficiencies.
Several suggestions were made to improve the quality of annual exams and traceability of records. (See Exit Comments)
M.L mu w-r
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OFFICIAL RECORD COPY MILLSTONE 1 EXAM RPT - 0005.0.0 1
-M OM {
09/21/84 kDR i
2 REPORT DETAILS TYPE OF EXAMS: Initial Replacement X
Requalification EXAM RESULTS:
1 RO l
SRO l
Inst. Cert i Fuel Handler l l Pass / Fail l
Pass / Fail l Pass / Fail l
Pass / Fall l
I I
I I
I I
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l IWritten Exam I
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CHIEF EXAMINER AT SITE: David Lange, US NRC, Region I 2.
OTHER EXAMINERS: John Berry, US NRC, Region I 3.
PERSONS EXAMINED SRO (Upgrade)"
Michael J. Bigiarelli William R. McCollum OFFICIAL RECORD COPY MILLSTONE 1 EXAM RPT - 0005.1.0 09/21/84 b
t 3
1.
Summary of generic strengths or deficiencies noted on oral exams:
- No generic deficiencies were noted during the oral exams.
- A generic strength was noted in the area of Reactivity Control and Transient Analysis.
2.
Summary of generic strengths or deficiencies noted from grading of written exams:
The written exam noted a generic weakness in Section Six (6), " Plant Systems Design, Control, and Instrumentation".
3.
Comments on availability of, and candidate familiarization with plant reference material in the control room:
- The control room reference material was readily available.
- The candidates were sufficiently knowledgeable in using the proper procedures.
4.
Comments on availability of, and candidate familiarization with design, procedure, and T. S. changes, and with LERs and recent significant events.
- In general, the candidates used the Technical Specifications and proce-dures effectively.
- 0ne examiner noted that a few candidates were inadequately aware of recent, significant industry events.
5.
Personnel Present at Exit Interview:
NRC Personnel John Berry, Chief BWR Examiner, US NRC,' Region I David Lange, BWR Examiner US NRC, Region I Lynn Banavitch, Examiner Trainee, US NRC, Region I Frank Crescenzo, Examiner Trainee, US NRC, Region I John T. Shediosky, Senior Resident Inspector, NRC Facility Personnel Neil G. Bergh, Unit I Operations Assistant Michael C. Jensen, Training Supervisor, MP U-1 Charles S. Marschall, Senior Instructor - Operator MP U-1 Ray Palmieri, MP1, Operations Supervisor Keith Parkinson, Supervisor Millstone Training Branch Ron Stotts, MP3 Training, NU OFFICIAL RECORD COPY MILLSTONE 1 EXAM RPT - 0006.0.0 09/21/84-i
4 6.
Summary of NRC Comments made at exit interview:
A.
The Chief Examiner noted that both (?) candidates clearly passed the oral examination.
B.
The plant was considered very clean and cooperation of the on-shift personnel in the control room was appreciated.
C.
The Requal Inspection conducted by the examiners on November 7,1984 produced no significant deficiencies, however, the following suggestions were made.
- Attendance sheets should be initialed by the class attendees at least once during the morning and afternoon sessions in order to verify attendance.
- A requal examination composed entirely of multiple choice questions may not be as effective as one with a mixture of question types.
=The filing system for the Requalification Program should be more organized and allow easy access to the information.
D.
The examiners urged the training staff not to hesitate in removing candidates that they feel are not ready to take the NRC Licensing Examinations.
E.
The examiners expressed the need for an established cutoff date for changes to procedures and other items included in the testable material. The candidates would not be responsible.for any change produced after this date.
This would provide consistency between the NRC written examinations and the candidates' study material.
F.
The examiners thanked the training staff for their cooperation, both during the examination period and the requal inspection.
7.
Summary of facility comments and commitments made at exit interview:
A.
The Training Department submitted the written comments on the SRO i
Exam. All comments, with the exception of question 6.07 and 8.10, had been previously resolved during the exam review conducted on 11/06/84.
B.
The Millstone Unit 1 Training Department noted the use of Tech. Spec.
scenerlo questions in Section 8 of the exam was a step in the l
positive direction for operationally oriented exam questions.
l C.
The Training Department committed to address the problem with the cut off date for both exam material and candidate withdrawal.
D.
The Millstone Training Department thanked the NRC Examiners for their j
professionalism during the week.
0FFICIAL RECCR0 COPY MILLSTONE 1 EXAM RPT - 0007.0.0 09/21/84
5 8.
CHANGES MADE TO WRITTEN EXAM DURING EXAMINATION REVIEW:
Question No.
Change Reason See the attachments addressing this topic.
--;m..nts:
1-Written Examination (s) and Answer Key (s) (SRO/RO) y 2.
Facility Comments on written examinations maae s uer exam Review 9
OFFICIAL RECORD COPY MILLSTONE.1 EXAM RPT - 0008.0.0 09/21/84
AUG 221985
.-n p f ', '
Docket Nos.
50-277 bU-2/6
-@ SEP U p 4 *.M Philadelphia Electric Company ATTN:
Mr. S. L. Daltroff Vice President Electric Production P' A" 2301 Market Street Philadelphia, Pennsylvania 19101 Gentlemen:
Subject:
Examination Report Nos. 50-277/85-22 (OL); 50-278/85-19 (0L)
This transmits the Examination Report of Operator Licensing Examinations conducted by USNRC Region I at the Peach Bottom Facility the week of June 25, 1985. At the exit interview held on June 27, 1985, the preliminary results of these examinations were discussed.
No reply to this letter is required.
Your cooperation in this ' matter is appreciated.
Sincerely, origir:1I:
I':' :
Samuel J. Collins, Chief Projects Branch No. 2 Division of Reactor Projects
Enclosure:
Examination Report Nos. 50-277/85-22 (OL); 50-278/85-19 (OL) cc w/ enclosures and attachments:
1 R. S. Fleischmann, Station Superintendent I
Plant Training Manager Senior Resident Inspector Publ i t-Onenmant Room (PDR)
(
Local Public Document Room (LPOR)
Nuclear Safety Information Center (NSIC) j Commonwealth of Pennsylvania i
~
?[f&hY
$77 l
PDR muu
"~~PDR O
0FFICIAL RECORD COPY OL 50-277/278/85 0001.0.0
{1 l
08/14/85 1
H<
Philadelphia Electric Company 2
cc w/ enclosures w/o attachments:
John S. Kemper, Vice President, Engineering and Research Troy B. Conner, Jr., Esquire A. J. Pietrofitta, General Manager, Power Production Engineering, Atlantic Electric Eugene J. Bradley, Esquire, Assistant General Counsel Raymond L. Hovis, Esquire Thomas Magette, Power Plant Siting, Nuclear Evaluations bec w/o attachment to enclosure:
ORP Section Chief Examiner Chief, OLB/0HFS, NRR OL File 12.0 Region I Docket Room (w/ concurrences)
Master Exam File l
l
-ar:RP
<,=0R.
.1,0,P R1,0RP
. RP DLange 3 Berry e
R llo HKister SCollins 8//i/85 8/l$/85 8//f/85
/$1 84))/85 8/$\\/85 0FFICIAL RECORD COPY OL 50-277/278/85 0002.0.0 08/19/85 l
k
U.S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT N05.
50-277/85-22 (OL); 50-278/85-19 (OL)
FACILITY DOCKET NOS.
50-277 and 50-278 FACILITY LICENSE NO.
Philadelphia Electric Company 2301 Market Street Philadelphia, Pennsylvania 19101 FACILITY:
Peach Bottom EXAMINATION DATE:
June 25, 1985 to June 27, 1985 9 /9!d CHIEF EXAMINER:
et <f.
D. Lange, ReaMor' Engindr Examiner
/ Dafe REVIEWED BY:
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((/ f 7 J. A. Terry, Lead BW7 Reactor Engineer -
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Examiner REVIEWED BY:
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. K. KeVer, ~ Chief, Projects Section 1C ' Date '
APPROVED BY:
L/ b H. B. Kist.6 Chief, Projects Branch Date No. 1
SUMMARY
On June 25, 1985, three SRO and one RO written examinations were administered at the Peach Bottom Atomic Power Station. Oral examinations were administered to two SRO Instructor Certification and one SRO Upgrade candidates on June 26 and 27, 1985.
All candidates passed both the written and oral examinations with no generic weaknesses noted.
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r REPORT DETAILS Exam Results:
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SRO l Inst. Cert l
l Pass / Fail l Pass / Fail l
Pa ss/ Fail l
l 1
1 I
I I
l l
1 IWritten Exam l 1/0 1
1/0 l
2/0 l
I I
I I
I I
I I
I I
l Oral Exam l
/
I 1/0 l
2/0 l
l l
l l
l l
l 1
1 l
l Overall l
1/0 1
1/0 1
2/0 l
I i
i l
I 1.
Chief Exa:niner at Site:
Dave Lange, USNRC, Region I 2.
Other Examiners:
Tcny Mendfola, USNRC, HDQ, OLB l
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3 1.
Overall, the SRO and RO candidates appeared to be well prepared for the written and oral examinations.
During the oral examinations, only one weakness was noted by the examiner in the area of procedures.
The candidates had difficulty locating and differentiating between some of the plant protection and emergency pro-cedures.
This problem was addressed at the exit meeting.
All candidates were knowledgeable of existing plant conditions and equip-ment location.
2.
Personnel Present at Exit Interview:
NRC Personnel Dave Lange, Chief Examiner, USNRC, Region I Tony Mendiola, Reactor Engineer Examiner, OLB, HDQ Herb Williams, Resident Inspector, USNRC, Peach Bottom Facility Personnel Steve Roberts, Operations Engineer Bob Bulmer, Superintendent, Nuclear Training Dennis McClellan, Training Instructor, Nuclear Training 3.
Summary of NRC Comments Made at Exit Interview:
a.
The Chief Examiner re-emphasized the candidates strengths and weak-nesses noted during the oral examinations.
b.
Cooperation of the control room staff and the training department personnel was appreciated.
c.
Plant conditions were clean and security and Health Physics access control was good.
d.
A problem with the E-4 Diesel Generator security card reader was identified.
In addition, the physical condition of the E-4 0/G door was poor.
Facility personnel agreed to correct this problem.
4.
Summary of Facility Comments and Commitments Made at Exit Interview:
The Superintendent of Nuclear Training commented on the relaxed atsnosphere created by the examiners and felt that this increased the quality of the oral examinations.
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ination(s) and Answer Kev (s) (SRO/R 2.
Facility C ts on Written Examinations Made After Exam Review l
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